ML19295C018
| ML19295C018 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/03/1975 |
| From: | Oconnor P Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| FOIA-80-550 NUDOCS 8010150721 | |
| Download: ML19295C018 (5) | |
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APR 0 31975 Docket No. 50-10 LICENSEE: CottONWEALTH EDISON COMPANY
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FACILITY: DRESDEN NUCLEAR POWER STATION, UNIT 1 SUFt%RY OF MEETING HELD ON MARCH 12, 1975 REGARDING TdB PROPOSED DRESDEN UNIT 1 DECONTAMINATION On March 12, 1975 representatives of the Commonwealth Edison Company
^g met with the NRC staff to provide additional infomation relating to the A list of the meeting proposed Dresden Unit I chemical decontamination.
il attendees is attached, Co=nonwealth Edison previously met on November 26, 1974, with the NRC staff to describe the proposed decontamination program and on December 19, 1974 submitted a preliminary licensing submittal which described the program development, identified tests completed and planned to assure solvent compatibility with reactor materials, and provided a preliminary safety evaluation and design basis for the decontamination program.
At the March 12, 1975 meeting, Commonwealth Edison's representatives discussed items which the staff had identified as the result of our review of the December 19, 1974 submittal. Significant points discussed are summarized below:
Quality Assurance - Commonwealth Edison stated that it will assure 1.
compliance with 10 CFR Part 50 Appendix B by carrying out the decon-tanination program in accordance with its approved Station Quality F
They further stated that they would document this Assurance Pregram.
intent in the licensing submittal for the decontamination project.
Environmental Considerations - Dr. David Harmer of Dow Industrial 2.
Service, Commonwealth Edison's prime contractor for the cleaning I-project, described the chemical nature of the Dow developed Troprietary An solvent and the chemical reactions associated with its use.
evaluation of the magnitude of hydrogen generation by the process was also presented.
Dr. David Hamer stated that the concentration of hydrogen would be maintained below explosive icvels by use of a g)l F
nitrogen blanket during cleaning and by dilution during venting d-
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operations.
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}2-An estimate of effluents produced based on " worst case assumptions",
was presented which identified the expected effluents from the system during each phase of the cleaning operation.
3.
Preliminary design layouts for the proposed radwaste facility were presented along with a listing of major equipment and components to be added. The radiological monitoring equipment proposed by the vendor was identified and a description of the proposed ventilation system was provided. Because the facility is in the preliminary design phase at this time it was noted that the final design m. differ in detail from that presented.
4.
The radiation protection program for the cleaning; operation will be under the direct supervision of a certified Health Physicist and two graduate health physicists from Dow Industrial Services. The program will be implemented by ten qualified radiation monitors ard Dow will assure that all aspects'of the project are planned in a manner to assure that occupational radiation exposures will be maintained as low as practicable.
Mr. Worden, Commonwealth Edison's project manager for the decontamination program, indicated that in addition to the health physics support provided by Dow Industrial Service, Commonwealth Edison, as the licensee, will exercise overall responsibility for assuring that occupational exposures are maintained as low as practicable for all personnel at the site.
A Man-Rem analysis for the decontakihation program was presented which estinates that less than 281 Man Rem will be received in the performance of the system decontamination. Coc:monwealth estimated that the successful L
cleaning would save approximately 500 W n-Rem per year over the remaining life time of the facility.
Commonwealth agreed to include in its licensing submittal, the radiation i
dose level criteria that will be applied to assure that occupational j~
doses will be maintained as low as practicable in uncontrolled areas surrounding the new radwaste building.
5.
The materials testing program carried out by Dow Industrial Service (DIS) was described and the results discussed. The testing program to date has not identified any material failures that are attributable to the cleaning solvent. In those tests that were carried to the point of material failure, the same failure properties were observed
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on control samples that had not been exposed to the Dow NS-1 solvent.
In addition to the testing program conducted by DIS, a program has been developed by General Electric to independently corroborate the DIS material testing program. The program will evaluate whether the everviy af 30A 99fringtheci,eaningcreratpon nnw univ e wi11 rano
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3-and will further evaluato whether exposure to the solvent makes 304 SS more susceptible to cracking in subsequent BWR servico.
6.
The following information was provided in response to questions raised by the Advisory Committes on Reactor Safeguards on March 7,1975:
Q.
What happens to the solvent under irradiation if it were circulated in the coolant?
A.
The solvent decomposes slightly under irradiation.
It decomposes rapidly into simple molecules whsn heated to reactor operating temperature. These molecules are detectable by conductivity measurements at very low concentrations and are rencYed by the reactor cleanup system, therefore the normal reactor coolant chenistry limits on conductivity provide assurance that the solvent has been completely removed by rinsing and preoperational testing with the cleanup system in service.
Q.
Is there an " operational window" of process temperature outside of which the solvent behaves in an anomlous manner in the event control of process temperature is lost?
[
l A.
The cleaning procedure includes the cooling down of the solvent and dissolved corrosion products prior to transferring them to the storage tanks. This step has been carried out in the solvent development program and does not cause redeposition of the solvent or dissolved corrosion products.
Commonwealth Edison agreed to include, in its final licensing submittal;,
discussion of the additional information presented orally at this meeting.
l M Q'i tm 7 s 9 n r ci l fc w I Lu 6 Tonp op Paul W. O'Connor Operating Reactors Branch #2 Division of Reactor Licensing Enclosure DISTRIBUTION:
Attendance List Docket s'
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Form AEC-518 (Rev. 9-53) AECM 0240 o*o e45 814 cs-1 445-c s
f ATTENDANCE LIST HEETING WInt C0feONNEALW EDISON CGiPANY MARCH 12, 197S f
C0tBONWEALW EDISON COMPANY W. Kiepaisch W. P. Worden R. F. Janecek T. S. Abel D. J. Scott DON INDUSTRIAL SERVICE D. E. Harmer F. P. Frauson, Jr.
T. P. Boyce SUNTAC NUCLEAR CORPORATION _
J. J. Ho11away A. F. Ciannavel GENEPAL ELECTRIC COMPANY T. E. Adams D. Dawson ARGONNE NATIONAL LAB C. F. Cheng NRC - STAFF P. W. O'Connor J. T. Conway J. W. Gilray D. T. Swanson R. Each W. Kreger S. Kirslis H. Conrad F.
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po su-ts-sises-s 643-c s Forro AEC-318 (Rev.9 53) AECM 0240
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4 DISTRIBlTTION FOR MEETING SUhB!ARY Dccket V. Bcuaroya R.11. Vollmer NRC PDR Local PDR B. R. Grimes NRR Reading W. P. Gammill ORB #2 Reading J. Kastner V. A. Moore M. Spangler R. C. DeYoung R. L. Ballard D. J. Skovholt EP Project Manager D. R. Muller Project Manager R. Denise Attorney, OELD K. R. Goller OISE (3)
W. R. Butler Licensing Assistant J. F. Stolz NRC Participants R. A. Clark R. Fraley, ACRS (14)
R. E. Ireland D. Vassallo K. Kniel
- 0. D. Parr A. Schwencer R. A. Purple P. F. Collins G. W. Knighton G. Dicker B. J. Youngblood 11. Regan G. Lear S. Varga T. J. Carter F. Schroeder R. R. Maccary V. Stello R. L. Tedesco
- 11. R. Denton J. P. Knight S. S. Pawlicki L. C. C. Shao T. M. Novak D. Ross R. W. liouston T. A. Ippolito C. G. Long G. C. Lainas I